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Yano, Yasuhide; Tanno, Takashi; Oka, Hiroshi; Otsuka, Satoshi; Kaito, Takeji
Journal of Nuclear Materials, 555, p.153105_1 - 153105_8, 2021/11
Times Cited Count：3 Percentile：10.00(Materials Science, Multidisciplinary)The aim of this study was to evaluate the tensile properties and microstructures of dissimilar welds between 11Cr-ferritic/martensitic steel and 316 stainless steel after thermal aging at temperatures between 400 and 600
C up to 30,000 h. Characterization of microstructure was carried out by scanning electron microscopy and transmission electron microscopy. Microstructural analysis showed that the microstructure in the weld metals consisted of lath martensite containing a small amount of residual austenite. Thermal aging hardening of WMs occurred at 400 and 450C due to the effects of both a-a' phase separation and G-phase precipitation. However, there was no significant change in the total elongation, and fracture surfaces indicated that very fine dimpled rupture was predominant rather than the cleavage rupture. It was suggested that lath martensite phases enhanced the tensile strength due to phase separation, while residual austenite played a role in keeping elongation as a soft phase.
Sato, Satoshi; Furuya, Kazuyuki; Hatano, Toshihisa; Kuroda, Toshimasa*; Enoeda, Mikio; Takatsu, Hideyuki; Ohara, Yoshihiro
JAERI-Tech 2000-042, 121 Pages, 2000/07
JAERI-Tech-2000-042.pdf:58.33MB
no abstracts in English
Tsuchiya, Kunihiko; Kawamura, Hiroshi;
Fusion Technology, 2, p.1399 - 1402, 1996/00
no abstracts in English
Tsuchiya, Kunihiko; Kawamura, Hiroshi
Journal of Nuclear Materials, 233-237(PT.B), p.913 - 917, 1996/00
Times Cited Count：38 Percentile：92.74(Materials Science, Multidisciplinary)no abstracts in English
Tsuchiya, Kunihiko; Kawamura, Hiroshi; Oyamada, Rokuro
JAERI-Tech 95-017, 72 Pages, 1995/03
no abstracts in English
immersionIshijima, Yasuhiro; Ueno, Fumiyoshi; Abe, Hitoshi; Igarashi, Takahiro
no journal, ,
In spent nuclear fuel reprocessing plants, there are components made of zirconium (Zr) and stainless steel (SUS) to match the corrosiveness of the reprocessing process, and because Zr and SUS have poor weldability, the components are connected by explosive joints with tantalum (Ta) between them. On the other hand, Ta corrodes with hydrogen generation in sodium hydroxide (NaOH) solution, which is expected to be used for decontamination of equipment, and also absorbs hydrogen and decreases ductility, so there is concern about hydrogen embrittlement of dissimilar joints due to decontamination. In this study, NaOH-HNO alternating immersion corrosion tests and electrochemical measurements were conducted on R-SUS304ULC/Ta/Zr dissimilar joints under the assumption of decontamination work in order to fundamentally investigate the corrosion and hydrogen absorption behavior of dissimilar joints due to decontamination. As a result, it was found that hydrogen absorption into Ta in the dissimilar materials was suppressed compared to that in pure Ta plates. From the results of electrochemical measurements, it is considered that the reason for this is that the cathodic reaction, which is the source of hydrogen generation, is separated on the SUS and Zr surfaces when Ta contacts SUS and Zr, and hydrogen adsorption is suppressed by the passivation of Ta.
